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{{#Wiki_filter:PVNGS License Examination Record of Rejected K/As PVNGS Form ES-401-4 Randomly Tier /                                            Reason for Rejection Group    Selected K/A No Ice Condenser System is available at PVNGS 2/1    3.5.025 2/2    3.5.027      No Containment Iodine Removal System is available at PVNGS 1/2    4.2.033      No IRM System is available at PVNGS 1/1    4.1.011EK3.10 (RO) PTS limits do not apply to a large break LOCA at PVNGS (RO) The MFP speed signal power is supplied from a Non-Vital AC bus at 1/1    4.2.057AA1.03 PVNGS. This KA is not applicable.
1/2    4.2.015AK1.03 (RO) Single RCP operation is not allowed at PVNGS 2/1    3.4.059A107  (RO) No ICS system is available at PVNGS 2/1    3.8.078K1.01  (RO) No Sensor Air System is available at PVNGS Confidential                          Page 1                                    05/05/05
 
PVNGS NRC License Examination July 29, 2005 PWR Written Examination Outline PVNGS Form ES-401-2 Tier            Group                            RO K/A Category Points                                  SRO-Only Points K    K    K    K    K  K    A    A    A    A    G    Total        K    A  A    G    Total 1    2    3    4    5  6    1    2    3    4
* 2    *
: 1.                  1          3    3    3                    3    3              3      18        0    0    5    1      6 Emergency &
Abnormal Plant            2          1    2    1                    1    2              2        9        0    0    3    1      4 Evolutions            Tier 4    5    4                    4    5              5      27        0    0    8    2      10 Totals 1          2    2    3    3    3    2    2    3    2    3  3      28        0    0    4    1      5 2.
Plant Systems            2          1    1    1    1    1    1    1    1    1    1  0      10        1    0    1    1      3 Tier 3    3    4    4    4    3    3    4    3    4  3      38        1    0    5    2      8 Totals
: 3. Generic Knowledge and Abilities                  1          2          3          4                  1    2    3    4 Categories                                                                          10                              7 3          2          2          3                  2    2    1    2
: 1.      Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A Note:
category shall not be less than two).
: 2.      The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
: 3.      Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
: 4.      Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
: 5.      Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 6.      Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
: 7.
* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
: 8.      On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
: 9.      For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
Confidential                                            4/26/05                                                      Page 1
 
PWR RO Examination Outline Facility:    PVNGS                                                                                            Printed:    05/05/2005 ES - 401                              Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1                      Form ES-401-2 E/APE # / Name / Safety Function            K1 K2    K3 A1 A2      G    KA Topic                                  Imp.      Points 000007 Reactor Trip - Stabilization -                  X                EK3.01 - Actions contained in EOP for          4.0      1 Recovery / 1                                                            reactor trip 000008 Pressurizer Vapor Space Accident / 3        X                    AK2.01 - Valves                              2.7*        1 000009 Small Break LOCA / 3                                X            EA1.10 - Safety parameter display            3.8*        1 system 000011 Large Break LOCA / 3                  X                          EK1.01 - Natural circulation and              4.1      1 cooling, including reflux boiling 000022 Loss of Rx Coolant Makeup / 2          X                          AK1.03 - Relationship between                  3.0      1 charging flow and PZR level 000025 Loss of RHR System / 4                      X                    AK2.03 - Service water or closed              2.7      1 cooling water pumps 000026 Loss of Component Cooling Water /                  X            AA1.03 - SWS as a backup to the              3.6*        1 8                                                                        CCWS 000027 Pressurizer Pressure Control System                          X 2.4.17 - Knowledge of EOP terms and              3.1      1 Malfunction / 3                                                          definitions.
000029 ATWS / 1                                    X                    EK2.06 - Breakers, relays, and              2.9*        1 disconnects 000038 Steam Gen. Tube Rupture / 3                                  X 2.1.30 - Ability to locate and operate          3.9      1 components, including local controls.
000040 Steam Line Rupture - Excessive Heat    X                          AK1.03 - RCS shrink and consequent            3.8      1 Transfer / 4                                                            depressurization 000054 Loss of Main Feedwater / 4                          X            AA1.02 - Manual startup of electric            4.4      1 and steam-driven AFW pumps 000055 Station Blackout / 6                                    X        EA2.02 - RCS core cooling through              4.4      1 natural circulation cooling to S/G 1
 
PWR RO Examination Outline Facility:  PVNGS                                                                                                Printed:    05/05/2005 ES - 401                            Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1                          Form ES-401-2 E/APE # / Name / Safety Function            K1 K2  K3 A1 A2      G    KA Topic                                      Imp.      Points cooling 000056 Loss of Off-site Power / 6                                  X 2.1.25 - Ability to obtain and interpret            2.8      1 station reference materials such as graphs, monographs, and tables which contain performance data.
000058 Loss of DC Power / 6                          X                AK3.01 - Use of dc control power by              3.4*        1 ED/Gs 000062 Loss of Nuclear Svc Water / 4                          X        AA2.06 - The length of time after the            2.8*        1 loss of SWS flow to a component before that component may be damaged 000065 Loss of Instrument Air / 8                    X                AK3.08 - Actions contained in EOP for              3.7      1 loss of instrument air CE/E06 Loss of Main Feedwater / 4                            X        EA2.2 - Adherence to appropriate                  3.0      1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 3    3  3  3    3    3                                      Group Point Total:      18 1
 
PWR RO Examination Outline Facility:  PVNGS                                                                                                Printed:    05/05/2005 ES - 401                            Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2                          Form ES-401-2 E/APE # / Name / Safety Function            K1 K2  K3 A1 A2      G    KA Topic                                      Imp.      Points 000036 Fuel Handling Accident / 8                X                    AK2.01 - Fuel handling equipment                  2.9      1 000060 Accidental Gaseous Radwaste Rel. /    X                        AK1.01 - Types of radiation, their units          2.5      1 9                                                                      of intensity and the location of sources of radiation in a nuclear reactor power plant 000061 ARM System Alarms / 7                                  X        AA2.05 - Need for area evacuation; check          3.5      1 against existing limits 000067 Plant Fire On-site / 9                                      X 2.1.20 - Ability to execute procedure                4.3      1 steps.
000068 Control Room Evac. / 8                                      X 2.1.10 - Knowledge of conditions and                2.7      1 limitations in the facility license.
000069 Loss of CTMT Integrity / 5                    X                AK3.01 - Guidance contained in EOP for          3.8*        1 loss of containment integrity CE/A11 RCS Overcooling - PTS / 4                        X            EA1.1 - Components, and functions of              3.3      1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features CE/A13 Natural Circ. / 4                                      X        EA2.2 - Adherence to appropriate                  2.9      1 procedures and operation within the limitations in the facility's license and amendments CE/A16 Excess RCS Leakage / 2                    X                    EK2.2 - Facility's heat removal systems,          3.0      1 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility K/A Category Totals: 1    2  1  1    2    2                                      Group Point Total:        9
 
PWR RO Examination Outline                                      Printed:
Facility:    PVNGS                                                                                                    05/05/2005 ES - 401                                  Plant Systems - Tier 2 / Group 1                                        Form ES-401-2 Sys/Evol # / Name                K1 K2 K3 K4 K5 K6 A1          A2  A3  A4 G KA Topic                          Imp. Points 003 Reactor Coolant Pump              X                                        K2.01 - RCPS                      3.1      1 004 Chemical and Volume Control                        X                        K6.31 - Seal injection            3.1      1 system and limits on flow range 004 Chemical and Volume Control                                              X  A4.10 - Boric acid pumps          3.6      1 005 Residual Heat Removal                          X                            K5.03 - Reactivity effects        2.9*    1 of RHR fill water 006 Emergency Core Cooling                X                                      K3.01 - RCS                        4.1*    1 007 Pressurizer Relief/Quench Tank                X                            K5.02 - Method of forming          3.1      1 a steam bubble in the PZR 007 Pressurizer Relief/Quench Tank  X                                            K1.03 - RCS                        3.0      1 008 Component Cooling Water        X                                            K1.02 - Loads cooled by            3.3      1 CCWS 008 Component Cooling Water                                                  X  A4.01 - CCW indications            3.3      1 and controls 010 Pressurizer Pressure Control      X                                        K2.01 - PZR heaters                3.0      1 010 Pressurizer Pressure Control                                            X  A4.02 - PZR heaters                3.6      1 012 Reactor Protection                        X                                  K4.09 - Separation of control      2.8      1 and protection circuits 013 Engineered Safety Features                    X                            K5.02 - Safety system logic        2.9      1 Actuation                                                                        and reliability 022 Containment Cooling                                            X            A2.03 - Fan motor thermal          2.6      1 overload/high-speed operation 026 Containment Spray                        X                                  K4.05 - Prevention of              2.8      1 material from clogging nozzles during recirculation 039 Main and Reheat Steam                    X                                  K4.04 - Utilization of            2.9      1 steam pressure program control when steam dumping through atmospheric relief/dump valves, including 1
 
PWR RO Examination Outline                                        Printed:
Facility:    PVNGS                                                                                                      05/05/2005 ES - 401                                      Plant Systems - Tier 2 / Group 1                                        Form ES-401-2 Sys/Evol # / Name                  K1 K2 K3 K4 K5 K6 A1            A2  A3  A4 G KA Topic                          Imp. Points T-ave. limits 059 Main Feedwater                                                                X 2.1.1 - Knowledge of              3.7      1 conduct of operations requirements.
061 Auxiliary/Emergency                                        X                  A1.02 - S/G pressure              3.3*      1 Feedwater 061 Auxiliary/Emergency                                  X                        K6.01 - Controllers and            2.5      1 Feedwater                                                                          positioners 062 AC Electrical Distribution              X                                      K3.01 - Major system loads        3.5      1 062 AC Electrical Distribution                                  X                  A1.01 - Significance of D/G        3.4      1 load limits 063 DC Electrical Distribution                                        X            A2.01 - Grounds                    2.5      1 064 Emergency Diesel Generator              X                                      K3.02 - ESFAS controlled or        4.2      1 actuated systems 064 Emergency Diesel Generator                                                    X 2.2.24 - Ability to analyze        2.6      1 the affect of maintenance activities on LCO status.
073 Process Radiation Monitoring                                      X            A2.02 - Detector failure          2.7      1 076 Service Water                                                          X        A3.02 - Emergency heat            3.7      1 loads 078 Instrument Air                                                                X 2.4.11 - Knowledge of              3.4      1 abnormal condition procedures.
103 Containment                                                            X        A3.01 - Containment                3.9      1 isolation K/A Category Totals:  2  2  3    3    3  2    2    3    2    3 3                    Group Point Total:      28 1
 
PWR RO Examination Outline                                      Printed:
Facility:    PVNGS                                                                                                      05/05/2005 ES - 401                                      Plant Systems - Tier 2 / Group 2                                      Form ES-401-2 Sys/Evol # / Name                  K1 K2 K3 K4 K5 K6 A1            A2  A3  A4 G KA Topic                        Imp. Points 001 Control Rod Drive                    X                                          K2.05 - M/G sets                  3.1*      1 002 Reactor Coolant                                  X                            K5.08 - Why PZR level            3.4      1 should be kept within the programmed band 011 Pressurizer Level Control                                  X                  A1.02 - Charging and              3.3      1 letdown flows 015 Nuclear Instrumentation                                                    X  A4.01 - Selection of              3.6*      1 controlling NIS channel 017 In-core Temperature Monitor                  X                                  K4.01 - Input to subcooling      3.4      1 monitors 033 Spent Fuel Pool Cooling          X                                            K1.05 - RWST                      2.7*      1 034 Fuel Handling Equipment                                                X        A3.01 - Travel limits            2.5*      1 056 Condensate                                                        X            A2.04 - Loss of condensate        2.6      1 pumps 071 Waste Gas Disposal                      X                                      K3.04 - Ventilation system        2.7      1 086 Fire Protection                                      X                        K6.04 - Fire, smoke, and          2.6      1 heat detectors K/A Category Totals:  1  1  1    1    1  1    1    1    1    1 0                    Group Point Total:      10 1
 
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline                                      Printed: 05/05/2005 Facility:  PVNGS                                                                                  Form ES-401-3 Generic Category                  KA      KA Topic                                                Imp. Points Conduct of Operations              2.1.16  Ability to operate plant phone, paging system,            2.9        1 and two-way radio.
2.1.27  Knowledge of system purpose and or function.              2.8        1 2.1.28  Knowledge of the purpose and function of major            3.2        1 system components and controls.
Category Total:                3 Equipment Control                  2.2.11  Knowledge of the process for controlling                  2.5        1 temporary changes.
2.2.27  Knowledge of the refueling process.                        2.6        1 Category Total:                2 Radiation Control                  2.3.4  Knowledge of radiation exposure limits and                2.5        1 contamination control, including permissible levels in excess of those authorized.
2.3.11  Ability to control radiation releases.                    2.7        1 Category Total:                2 Emergency Procedures/Plan          2.4.13  Knowledge of crew roles and responsibilities              3.3        1 during EOP flowchart use.
2.4.19  Knowledge of EOP layout, symbols, and icons.              2.7        1 1
 
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline                                Printed: 05/05/2005 Facility:  PVNGS                                                                        Form ES-401-3 Generic Category                KA      KA Topic                                          Imp. Points 2.4.43  Knowledge of emergency communications systems        2.8        1 and techniques.
Category Total:                3 Generic Total:                10 1
 
PWR SRO Examination Outline Facility:    PVNGS                                                                                          Printed:    05/05/2005 ES - 401                              Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1                      Form ES-401-2 E/APE # / Name / Safety Function            K1 K2    K3 A1 A2      G    KA Topic                                Imp.      Points 000007 Reactor Trip - Stabilization -                          X        EA2.01 - Decreasing power level, from        4.3      1 Recovery / 1                                                            available indications 000015/000017 RCP Malfunctions / 4                            X        AA2.10 - When to secure RCPs on loss of      3.7      1 cooling or seal injection 000025 Loss of RHR System / 4                                  X        AA2.02 - Leakage of reactor coolant          3.8      1 from RHR into closed cooling water system or into reactor building atmosphere 000040 Steam Line Rupture - Excessive Heat                    X        AA2.05 - When ESFAS systems may be            4.5      1 Transfer / 4                                                            secured 000058 Loss of DC Power / 6                                        X 2.4.4 - Ability to recognize abnormal          4.3      1 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
000062 Loss of Nuclear Svc Water / 4                          X        AA2.02 - The cause of possible SWS            3.6      1 loss K/A Category Totals:  0    0  0  0    5    1                                  Group Point Total:      6 1
 
PWR SRO Examination Outline Facility:  PVNGS                                                                                                  Printed:    05/05/2005 ES - 401                              Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2                          Form ES-401-2 E/APE # / Name / Safety Function            K1 K2    K3 A1 A2      G    KA Topic                                      Imp.      Points 000003 Dropped Control Rod / 1                                  X        AA2.04 - Rod motion stops due to                3.6*        1 dropped rod 000028 Pressurizer Level Malfunction / 2                        X        AA2.03 - Charging subsystem flow                  3.3      1 indicator and controller CE/A11 RCS Overcooling - PTS / 4                                    X 2.1.20 - Ability to execute procedure                4.2      1 steps.
CE/A16 Excess RCS Leakage / 2                                  X        EA2.2 - Adherence to appropriate                  3.7      1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals:  0    0  0  0    3    1                                      Group Point Total:        4 1
 
PWR SRO Examination Outline                                        Printed:
Facility:    PVNGS                                                                                                      05/05/2005 ES - 401                                      Plant Systems - Tier 2 / Group 1                                        Form ES-401-2 Sys/Evol # / Name                  K1 K2 K3 K4 K5 K6 A1            A2  A3  A4 G KA Topic                          Imp. Points 003 Reactor Coolant Pump                                                          X 2.2.22 - Knowledge of              4.1      1 limiting conditions for operations and safety limits.
005 Residual Heat Removal                                            X            A2.04 - RHR valve                  2.9      1 malfunction 012 Reactor Protection                                                X            A2.01 - Faulty bistable            3.6      1 operation 076 Service Water                                                    X            A2.01 - Loss of SWS                3.7*    1 103 Containment                                                      X            A2.04 - Containment                3.6*    1 evacuation (including recognition of the alarm)
K/A Category Totals:  0  0  0    0    0  0    0    4    0    0 1                    Group Point Total:      5 1
 
PWR SRO Examination Outline                                      Printed:
Facility:    PVNGS                                                                                                    05/05/2005 ES - 401                                      Plant Systems - Tier 2 / Group 2                                      Form ES-401-2 Sys/Evol # / Name                  K1 K2 K3 K4 K5 K6 A1            A2  A3  A4 G KA Topic                        Imp. Points 034 Fuel Handling Equipment          X                                            K1.05 - Shutdown monitor        3.4*    1 056 Condensate                                                        X            A2.05 - Condenser tube          2.5*    1 leakage 072 Area Radiation Monitoring                                                    X 2.4.29 - Knowledge of the        4.0      1 emergency plan.
K/A Category Totals:  1  0  0    0    0  0    0    1    0    0 1                  Group Point Total:      3 1
 
Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline                                      Printed: 05/05/2005 Facility:  PVNGS                                                                                    Form ES-401-3 Generic Category                  KA        KA Topic                                                Imp. Points Conduct of Operations              2.1.6  Ability to supervise and assume a management role          4.3        1 during plant transients and upset conditions.
2.1.11  Knowledge of less than one hour technical                  3.8        1 specification action statements for systems.
Category Total:                2 Equipment Control                  2.2.25  Knowledge of bases in technical specifications for          3.7        1 limiting conditions for operations and safety limits.
2.2.34  Knowledge of the process for determining the                3.2*      1 internal and external effects on core reactivity.
Category Total:                2 Radiation Control                  2.3.6  Knowledge of the requirements for reviewing and            3.1        1 approving release permits.
Category Total:                1 Emergency Procedures/Plan          2.4.26  Knowledge of facility protection requirements              3.3        1 including fire brigade and portable fire fighting equipment usage.
2.4.30  Knowledge of which events related to system                3.6        1 operations/status should be reported to outside agencies.
Category Total:                2 Generic Total:                  7 1
 
Appendix    D                          Scenario Outline                            Form ES-D-1 Facility: PVNGS                  Scenario No.:            1                Op-Test No:    2005 Examiners:                                                Operators:
Initial Conditions: IC #16, 50% power, MOC.
Turnover: Unit 1 has been at ~50% power for the past 3 days. The Unit had previously operated at near 100% power for 8 months. Power was reduced to perform repairs on A MFP. The repairs have been completed and the Unit is now waiting on a chemistry hold to increase power back to 100%. AF A is tagged out for maintenance. LCO 3.7.5. Condition b has been entered. Expected to be returned in 12 hours. HPSI A tagged out for bearing replacement. LCO 3.5.3 condition b was entered 4 hours ago. Expected to be returned in approximately 15 hours. Train B is protected equipment. Normal Shiftly Surveillances are complete. EOOS action level is Orange.
Event      Malf. No.      Event Type*                                        Event Description No.
1        ED04A              C-SRO      After turnover is complete, Startup Transformer NAN-X01 fails (Plant Event) requiring an evaluation of operability of AC offsite circuits, Tech Spec 3.8.1.1 operability must be performed within 1 hr.
2        TCNP01A              C-CO      After the crew evaluates TS for the SUT failure, TCW pump A bearing seizes.
This causes the A TCW Pump to trip on overcurrent. The Standby pump does not auto start. The crew should implement 41AL-1RK7A & 40AO-9ZZ03, Loss of Cooling Water, Section 5.0 and manually start the Standby TCW Pump.
3                          I-RO/SRO      After the crew addresses the loss of cooling water, the Reactor Regulating System TR04:RCNTT                        Hot Leg temperature transmitter 111X input fails low affecting the PZR Level 111X                          Control Setpoint. The crew should implement 40AO-9ZZ16, RRS Malfunctions, Section 3.0, and select the unaffected instrument for input.
4                        C-RO/SRO      While the crew is implementing 40AO-9ZZ16, the in-service letdown back-AV02:CHEP                        pressure control valve fails closed. The crew should implement 40AO-9ZZ05, V201Q                        Loss of Letdown, Section 3.0.
5        TH01A .01        C -RO/SRO      After the crew places the alternate letdown back-pressure control valve in service, 5:00                        an RCS leak in excess of Tech Spec limits occurs. The crew should implement CV06A                          40AO-9ZZ02, Excessive RCS Leakrate, and evaluate T.S. 3.4.14. The normally running charging pump trips requiring the RO to start the E Charging Pump.
6          RD03I              C-        After the crew addresses the RCS leak, two CEAs drop partially into the core. A RO/CO/SRO      reactor trip is automatically initiated. Two stuck CEAs require the RO to initiate RD03J M- All      boration. The main turbine will fail to trip requiring the CO to manually trip it. The RD02A                          crew should implement 40EP-9EO01, Standard Post Trip Actions.
RD02C                          (Critical Task to establish reactivity control)
TC18 7        NoMSIS            I-CO/RO      After boration is initiated and the crew has transitioned to 40EP-9EO03, Loss of MMF TH01A              M-All      Coolant Accident. The leak degrades into a Large Break LOCA. MSIS fails to
                .1                        automatically actuate, requiring manual actuation. B HPSI fails to auto start on the SIAS condition and requires a manual start.
End                                      Crew takes action to establish a cooldown.
point (Critical Task is to ensure adequate Safety Injection Actuation flow to meet Safety Function requirements within 30 minutes of entry into the LOCA procedure and after the Safety Injection Actuation setpoints are exceeded.)
          * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
 
Appendix  D                      Scenario Outline                            Form ES-D-1 (Critical Task is to stop the RCPs on loss of subcooling.)
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
 
Appendix    D                        Scenario Outline                              Form ES-D-1 Facility: PVNGS                  Scenario No.:            2                Op-Test No:      2005 Examiners:                                                Operators:
Initial Conditions: IC #20, 100% power, MOC.
Turnover: Unit 1 has been at 100% power for the last 8 months. AF A is tagged out for maintenance. LCO 3.7.5.
Condition b has been entered. Expected to be returned in 12 hours. HPSI A tagged out for bearing replacement.
LCO 3.5.3 condition b was entered 4 hours ago. Expected to return in approximately 15 hours. Normal Shiftly Surveillances are complete. Train B is protected equipment. EOOS action level is Orange.
Event        Malf. No.          Event                                  Event Description No.                              Type*
1            IOR              I-SRO        After the crew assumes the shift, the crew receives a High Log Power ZDSBAC01HLO                          Trip on Channel 'A' along with the High Log Power Permissive alarm.
G OFF                          The crew should recognize that the log power channel has not failed, but the permissive is no longer bypassed. The CRS should address Tech Specs. LCO 3.3.1 condition 'c' applies due to the bypass removal being inoperable and bypass or trip the channel within 1 hr.
2      BK05:NANS02G            R-RO        After the crew takes the LCO action, a loss of NAN-S02G will occur causing a loss of one tower of cooling tower fans. (Plant Event) The N-CO/SRO        CRS should enter 40AO-9ZZ12, Degraded Electrical and 40AO-9ZZ07, Degraded Vacuum. The crew determines a downpower is needed to stabilize vacuum.
After the crew completes the initial downpower, vacuum stabilizes.
3                              I-RO        After recovering from the loss of vacuum, a high failure of pressurizer TR01:RCNPT100                        pressure instrument RCN-PT-100X occurs. This will require the crew X 2500                              to address the alarm response procedure and select Channel Y on RCN-HS-100, PZR Pressure Control Selector, to ensure closer of the PZR spray valve.
4            CC01A          C-CO/SRO      After completing the actions for the PZR instrument failure, NCW Pump A will trip due to a ground fault. The Standby NCW pump CP05:NCNP01B                        will not start automatically or manually. This will require the CC01B                          operators to crosstie EW to NC IAW 40AO-9ZZ03, Loss of Cooling Water, Section 4.0. The CRS should address Tech Spec 3.7.7.
(Cascading T.S.)
C-RO/SRO      The RO should respond to the loss of letdown and refer to 40AO-9ZZ05. The CRS should take action to keep PZR level below the Tech. Spec. limit of 56%.
5            RD04              M-All        After the CRS has addressed Tech Specs, FWPT B alarms are received and the operator locally confirms high vibrations on the ATWS            C-RO/CO pump. The CO takes action to trip the B MFW pump. Reactor Power Cutback automatically initiates but two of the CEAs fail to insert. The reactor fails to trip automatically or by manual pushbuttons. The crew will open L-03 & L-10 breakers to initiate the
    * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
 
Appendix  D                      Scenario Outline                            Form ES-D-1 Rx Trip. All rods go in on the Reactor Trip. The crew should implement SPTAs.
(Critical Task to trip the Reactor)
The CRS should transition to the Rx Trip EOP.
6        ED02            C-CO      During implementation of Rx Trip, a loss of offsite power occurs. The CRS should transition to the LOOP/LOFC EOP. Once the crew enters CP06:SPBP01        M-All the LOOP/LOFC procedure a loss of PBB-S04 will occur because the B Spray Pond trips requiring the operator to secure the B DG.
The CO will need to swap the S/G feed source from AF B to AFN-P01.
7      CP06:AFNP01                  After the CO transitions to the N AF Pump, AFN-P01 will trip on an 86 Lockout. This will result in a loss of all feedwater.
8                          C-      The CRS should transition to the FRP procedure and restore power to SRO/RO/CO    PBB-S04 using the A DG. The crew can then feed the SGs with AF B.
M-All (PRA Significant)
(Critical Task to ensure the required 4KV bus is energized to meet Safety Function requirements prior to the completion of the Maintenance of Vital Auxiliaries success path)
(Critical Task to establish feedwater to the unaffected SG)
End                                    Crew stabilizes plant with AF B feeding at least one SG.
point
  * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
 
Appendix    D                        Scenario Outline                            Form ES-D-1 Facility: PVNGS                Scenario No.:            3                Op-Test No:    2005 Examiners:                                                Operators:
Initial Conditions: IC #20, 100% power, MOC.
Turnover: Unit 1 has been at 100% power for the last 8 months. AF A is tagged out for maintenance. LCO 3.7.5.
Condition b has been entered. Expected to be returned in 12 hours. HPSI A tagged out for bearing replacement.
LCO 3.5.3 condition b was entered 4 hours ago. Expected to return in approximately 15 hours. Normal Shiftly Surveillances are complete. Train B is protected equipment. EOOS action level is Orange.
Event          Malf. No.          Event                                    Event Description No.                              Type*
1        RCCPT101C            I-SRO        After the crew assumes the shift, the crew receives a high failure of C Channel Narrow Range Pressurizer Pressure Instrument. The crew should recognize the failure and respond with 41AL-1RK5A and T.S.
3.3.1.A. The crew takes action to bypass the affected parameters.
2            TH06A              C-SRO        After the crew takes the LCO action, a 30 gpd tube leak will start on
                                                #1 S/G. The crew should respond with 40AO-9ZZ02, Excessive RCS Leakrate, and notify chemistry. This Leakrate requires continued monitoring.
3            ED12B                C-        After the crew completes the applicable portions of 40AO-9ZZ02, RO/CO/SRO        PNB-D26 will be lost. The CRS should implement 40AO-9ZZ13, Loss of Class Instrument or Control Power, and select the appropriate control instrument for PZR level control, stop one charging pump, and goes to 40AO-9ZZ05, Loss of Letdown. CO starts 40ST-9EC03 within one hour and set CEAC INOP flag in all operable CPCs. CRS refers to T.S. 3.8.9 and 3.4.9.
4            NI02C 0              I-        After carrying out the actions for the loss of PNB-D26, Control RO/CO/SRO        Channel #2 will fail low. The crew should address the alarm response NI02D 0                          for the AMI received and respond IAW 40AO-9ZZ16, RRS Malfunction. The RO should take CEDMCS out of Auto Sequential and the CO should select the unaffected channel on RRS panel and place CEDMCS back to Auto Sequential. The CO will then take Control Channel #2 FWCS input to maintenance and remove the ATUN lockout.
5            TH06A                N-        After completing the actions for the loss of Control Channel #2, the RO/CO/CRS        S/G tube leak will degrade to 200 gpd. This will require the CRS to commence a plant Shutdown IAW 40OP-9ZZ05. T.S. 3.4.14.
6      TR01:RCNTT111Y            I- CO        During the shutdown the leak rate will degrade requiring a Unit Trip.
650                            The crew should enter the SPTAs, 40EP-9EO01. Upon entering the M-All        SPTAs, the Tave input to the FWCS will fail high causing the ruptured SG to be overfed. The CO will need to take action to minimize feed to the SG.
7            RP07B          C-RO/SRO        Train B BOP ESFAS Sequencer failure will occur on the trip. The RO should respond by manually starting B Train Safety Injection
    * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
 
Appendix  D                      Scenario Outline                            Form ES-D-1 and Support Equipment.
(Critical Task is to start B HPSI pump.)
M-All      After completing the SPTAs, the CRS should transition to the SGTR EOP, 40EP-9EO04 and proceeds to cooldown and isolate the ruptured S/G.
(Critical Task is to ensure the crew prevents a release of steam to atmosphere from the ruptured S/G during the RCS cooldown.)
(Critical Task is to ensure the crew isolates the most affected S/G within 30 minutes of entry into the SGTR procedure.)
End                                      Crew isolates the affected SG.
point (Critical Task is to ensure the crew takes action to prevent the Main Steam Safety Valves on the most affected S/G from opening after the most affected S/G has been isolated.)
  * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
 
PVNGS License Examination Administrative Topics Outline PVNGS Form ES-301-1 Facility: Palo Verde                                                      Date of Examination: 7/29/05 - 8/5/05 Examination Level: RO                                                      Operating Test Number: PVNGS RO Administrative Topic          Type      Describe activity to be performed:                              K/A #
(see Note)            Code*                                                                      IMP C, N      Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain Conduct of Operations                    performance data.                                              2.1.25 (Candidate will be required to calculate the required SDM        2.8 using procedures and given plant parameters)
Scheduled as Admin Task RA1-1. (NEW)
C, D      Ability to use plant computer to obtain and evaluate Conduct of Operations                    parametric information on system or component status.          2.1.19 (Candidate will be required to calculate NKBDELT).                3.0 Scheduled as Admin Task RA1-2. (AD010)
C, N      Knowledge of tagging and clearance procedures.
(Candidate will determine tagging boundaries for a              2.2.13 Equipment Control                        permit)                                                          3.6 Schedule as Admin JPM RA2. (NEW)
C, M Verify administrative and radiological entry requirements per the RWP (Candidate will be required to demonstrate Radiation Control                        the proper method for verifying qualifications and identify    2.3.1 the proper REP, task, and dose settings/limits for the            2.6 particular job assignment.)
Scheduled as Admin JPM RA3.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
*Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs:  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
(S)imulator Confidential                              Page 1                                  05/05/05
 
PVNGS License Examination                  PVNGS Form ES-301-1 Administrative Topics Outline Facility: Palo Verde                                                      Date of Examination: 7/29/05 - 8/5/05 Examination Level: SRO                                                    Operating Test Number: PVNGS SRO Administrative Topic          Type      Describe activity to be performed:                              K/A #
(see Note)            Code*                                                                        IMP C, M      Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.                                                2.1.25 Conduct of Operations                    (Candidate will be required to review a SDM surveillance          3.1 Test, indentify 3 errors and any required action)
Scheduled as Admin Task SA1-1.
C, N      Ability to locate and use procedures and directives related to shift staffing and activities.
(Candidate will be required to determine that operator is to 2.1.5 Conduct of Operations                    not able to stand watch and that the operator will need a          3.4 working hour limit deviation form to permit helping with surveillance)
Scheduled as Admin Task SA1-2. (NEW)
C, D      Knowledge of tagging and clearance procedures.
2.2.13 Equipment Control                        (Tech Review a Permit and determine three errors)                  3.8 Schedule as Admin JPM SA2.
C, D      Verify administrative and radiological entry requirements per the RWP (Candidate will be required to demonstrate the proper method for verifying qualifications and identify      2.3.1 Radiation Control                                                                                          3.0 the proper REP, task, and dose settings/limits for the particular job assignment.)
Scheduled as Admin JPM SA3.
S, M      Ability to take action called for in the Emergency Plan, including acting as Emergency Coordinator. (Candidate 2.4.38 Emergency Plan                          will classify event and perform initial Emergency                  4.0 Coordinator duties.)
Scheduled as Admin JPM SA4.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
*Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs:  4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
(S)imulator Confidential                                Page 1                                  05/05/05
 
PVNGS License Examination                            PVNGS Form ES301-2 Control Room/In-Plant Systems Outline Facility: PVNGS_                                          Date of Examination: 8/1/05 Exam Level: RO_                                            Operating Test No.: RO Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
JPM #      System/JPM Title                                          Type Code*                          Safety Function SAM JS1        Respond to a SIT Low Lvl alarm & Refill 3.2.006A4.02            4.0/3.8        2 Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the                    SAD JS2 Unit Auxiliary Transformer MAN-X02                        3.6.062.A4.07            3.1/3.1        6 SLN JS3        Perform BDAS Alarm Check (Appendix 8) w/i one 3.7.015.A3.03          3.9/3.9          7 hour (Time Critical)
SADL JS4        Vent off the high pressure in the reactor vessel head to 3.2.002.K4.05          3.8/4.2        3 the RDT. (RC001)
SAM JS5        Perform a Boration of the RCS (CH002 Modify, BAMP 3.1.004A4.01            3.8/3.9        1 Dish Press Lo Alarm received) Plant Event Reconnect and reset the Steam Bypass Control System                    SD                        4 JS6 (SF006)                                                  3.4.041.A4.08            3.0/3.1    (Secondary)
SN JS7        Respond to Containment Sump Trouble Excessive 3.5.103.A4.01          3.2/3.3        5 Runtime Alarm 41AL-1RK7B SD JS8        Vent the Containment (CP001)                                                                      8 3.8.029.A103            3.0/3.3 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
AEM JP1        Return a Battery Charger to Service (Attachment 97-A) 3.6.063.A4.02        2.8*/2.9          6 3.6.063.K1.03          2.9/3.5 Line up a Borated Water Source during Control Room                    DER                        1 JP2 Fire (PRA Significant) (AO017)                            4.2.068.AA1.11          4.0/4.3 Restore local air to the SFP gate seals and place the                EMPR JP3 Nitrogen bottles on standby (Plant Modification)          3.8.078.A3.01          3.1/3.2        8 3.8.078.K4.02            3.2/3.5
@      All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                              *Type Codes                                    Criteria for RO / SRO-I / SRO-U (A)lternate Path                                                                        4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from bank                                                                      9/8/4 (E)mergency or abnormal in-plant                                                        1/1/1 (L)ow-Power                                                                              1/1/1 (N)ew or (M)odified from bank including 1(A)                                            2/2/1 (P)revious 2 exams                                                            3 /  3 /  2 (randomly selected)
(R)CA                                                                                    1/1/1 (S)imulator Confidential                            Page 1
 
PVNGS License Examination                              PVNGS Form ES301-2 Control Room/In-Plant Systems Outline Facility: PVNGS                                          Date of Examination: 8/1/05 Exam Level: SRO                                          Operating Test No.: SROU Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
JPM #      System/JPM Title                                          Type Code*                          Safety Function SAM JS1        Respond to a SIT Low Lvl alarm & Refill 3.2.006A4.02              4.0/3.8        2 Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the                    SAD JS2 Unit Auxiliary Transformer MAN-X02                        3.6.062.A4.07            3.1/3.1        6 SLN JS3        Perform BDAS Alarm Check (Appendix 8) w/i one 3.7.015.A3.03            3.9/3.9          7 hour (Time Critical)
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
AEM JP1        Return a Battery Charger to Service (Attachment 97-A) 3.6.063.A4.02          2.8*/2.9          6 3.6.063.K1.03            2.9/3.5 Line up a Borated Water Source during Control Room                    DER                          1 JP2 Fire (PRA Significant) (AO017)                            4.2.068.AA1.11            4.0/4.3
@      All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
                            *Type Codes                                      Criteria for RO / SRO-I / SRO-U (A)lternate Path                                                                          4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from bank                                                                        9/8/4 (E)mergency or abnormal in-plant                                                          1/1/1 (L)ow-Power                                                                              1/1/1 (N)ew or (M)odified from bank including 1(A)                                              2/2/1 (P)revious 2 exams                                                            3 /  3 /  2 (randomly selected)
(R)CA                                                                                    1/1/1 (S)imulator Confidential                              Page 1
 
ES-301                                          Transient and Event Checklist                                    Form ES-301-5 Facility: PVNGS                                    Date of Exam: 7/29/05 - 8/05/05                Operating Test No.: 2005 A          E                                                          Scenarios P          V P          E                1                          2                        3                      4              T      M L          N                                                                (SPARE)                                    O      I I          T      CREW POSITION            CREW POSITION            CREW POSITION          CREW POSITION            T      N C                                                                                                                        A      I A          T                                                                                                            L      M N          Y        S        A        B      S        A        B      S        A      B      S        A      B              U T          P        R        T        O      R        T      O      R        T      O      R        T      O            M E        O        C        P      O        C        P      O        C      P      O        C      P RO          RX          0                          0                        0                                              0    1*
NOR        0                          1                        1                                              1    1*
SRO-I I/C        4                          3                        5                                              7    4*
MAJ        2                          3                        2                                              5    2 SRO-U TS          2                          2                        3                                              4    2 RO          RX                    0                                0                0                                      0    1*
NOR                  0                                1                1                                      1    1*
SRO-I I/C                  5                                4                3                                      9    4*
MAJ                  2                                3                2                                      5    2 SRO-U TS                    0                                0                0                                      0    NA RO          RX                            0                1                                0                              1    1*
NOR                          0                0                                1                              0    1*
SRO-I I/C                          3                4                                3                              7    4*
MAJ                          2                3                                2                              5    2 SRO-U TS                            0                0                                0                              0    NA Instructions:
: 1.        Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
: 2.          Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.
* Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
: 3.        Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirement.
Author:          _Phillip Capehart                      _______________________
NRC Reviewer:              _                          ________________________
 
ES-301                            Competencies Checklist                          Form ES-301-6 OPERATING TEST NO.: PVNGS 2005 SROU                      RO                BOP (CO)
Competencies                    SCENARIO                SCENARIO              SCENARIO 1      2      3  4    1      2    3    4    1      2    3  4 Interpret/Diagnose Events      1,2,3  1,2,4  1,2,3    3,4,5  2,3,4 2,3,4    2,6,7  2,4,5 2,3,4 and Conditions            4,5,6  5,6,8  4,5,6      6,7  5,6,8 5,6,7            6,7,8 5,6,7 7            7 Comply With and            1,2,3  1,2,4  1,2,3    3,4,5  2,3,4 2,3,4    2,5,6  2,4,5 2,3,4 Use Procedures (1)          4,5,6  5,6,8  4,5,6      6,7  5,6,8 5,6,7      7    6,8  5,6,7 7            7 Operate Control            NA    NA    NA      3,4,5  2,3,4 3,4,5    2,6,7  2,4,5 3,4,5 Boards (2)                                      6,7  5,6,8  6,7              6,8  6,7 Communicate and            1,2,3  1,2,3  1,2,3    3,4,5  2,3,4 2,3,4    2,6,7  2,4,5 2,3,4 Interact              4,5,6  4,5,6  4,5,6      6,7  5,6,8 5,6,7            6,7,8 5,6,7 7    7,8    7 Demonstrate Supervisory        1,2,3  1,2,4  1,2,3      NA    NA    NA        NA    NA    NA Ability (3)            4,5,6  5,6,8  4,5,6 7            7 Comply With and              1,5  1,4,5  1,3,5      NA    NA    NA        NA    NA    NA Use Tech. Specs. (3)
Notes:
(1) Includes technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Circle the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
Author:                Phillip Capehart      ___________________________
NRC Reviewer:                              ____________________________
NUREG-1021, Revision 9}}

Latest revision as of 23:45, 23 November 2019

008-2005 - Initial Draft Examination Outline
ML053330595
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 08/31/2005
From:
NRC Region 4
To:
Arizona Public Service Co
References
50-528/05-301, 50-529/05-301, 50-530/05-301
Download: ML053330595 (27)
v • d • e


Text

PVNGS License Examination Record of Rejected K/As PVNGS Form ES-401-4 Randomly Tier / Reason for Rejection Group Selected K/A No Ice Condenser System is available at PVNGS 2/1 3.5.025 2/2 3.5.027 No Containment Iodine Removal System is available at PVNGS 1/2 4.2.033 No IRM System is available at PVNGS 1/1 4.1.011EK3.10 (RO) PTS limits do not apply to a large break LOCA at PVNGS (RO) The MFP speed signal power is supplied from a Non-Vital AC bus at 1/1 4.2.057AA1.03 PVNGS. This KA is not applicable.

1/2 4.2.015AK1.03 (RO) Single RCP operation is not allowed at PVNGS 2/1 3.4.059A107 (RO) No ICS system is available at PVNGS 2/1 3.8.078K1.01 (RO) No Sensor Air System is available at PVNGS Confidential Page 1 05/05/05

PVNGS NRC License Examination July 29, 2005 PWR Written Examination Outline PVNGS Form ES-401-2 Tier Group RO K/A Category Points SRO-Only Points K K K K K K A A A A G Total K A A G Total 1 2 3 4 5 6 1 2 3 4

  • 2 *
1. 1 3 3 3 3 3 3 18 0 0 5 1 6 Emergency &

Abnormal Plant 2 1 2 1 1 2 2 9 0 0 3 1 4 Evolutions Tier 4 5 4 4 5 5 27 0 0 8 2 10 Totals 1 2 2 3 3 3 2 2 3 2 3 3 28 0 0 4 1 5 2.

Plant Systems 2 1 1 1 1 1 1 1 1 1 1 0 10 1 0 1 1 3 Tier 3 3 4 4 4 3 3 4 3 4 3 38 1 0 5 2 8 Totals

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 10 7 3 2 2 3 2 2 1 2
1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A Note:

category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.
  • The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

Confidential 4/26/05 Page 1

PWR RO Examination Outline Facility: PVNGS Printed: 05/05/2005 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - X EK3.01 - Actions contained in EOP for 4.0 1 Recovery / 1 reactor trip 000008 Pressurizer Vapor Space Accident / 3 X AK2.01 - Valves 2.7* 1 000009 Small Break LOCA / 3 X EA1.10 - Safety parameter display 3.8* 1 system 000011 Large Break LOCA / 3 X EK1.01 - Natural circulation and 4.1 1 cooling, including reflux boiling 000022 Loss of Rx Coolant Makeup / 2 X AK1.03 - Relationship between 3.0 1 charging flow and PZR level 000025 Loss of RHR System / 4 X AK2.03 - Service water or closed 2.7 1 cooling water pumps 000026 Loss of Component Cooling Water / X AA1.03 - SWS as a backup to the 3.6* 1 8 CCWS 000027 Pressurizer Pressure Control System X 2.4.17 - Knowledge of EOP terms and 3.1 1 Malfunction / 3 definitions.

000029 ATWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1 disconnects 000038 Steam Gen. Tube Rupture / 3 X 2.1.30 - Ability to locate and operate 3.9 1 components, including local controls.

000040 Steam Line Rupture - Excessive Heat X AK1.03 - RCS shrink and consequent 3.8 1 Transfer / 4 depressurization 000054 Loss of Main Feedwater / 4 X AA1.02 - Manual startup of electric 4.4 1 and steam-driven AFW pumps 000055 Station Blackout / 6 X EA2.02 - RCS core cooling through 4.4 1 natural circulation cooling to S/G 1

PWR RO Examination Outline Facility: PVNGS Printed: 05/05/2005 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points cooling 000056 Loss of Off-site Power / 6 X 2.1.25 - Ability to obtain and interpret 2.8 1 station reference materials such as graphs, monographs, and tables which contain performance data.

000058 Loss of DC Power / 6 X AK3.01 - Use of dc control power by 3.4* 1 ED/Gs 000062 Loss of Nuclear Svc Water / 4 X AA2.06 - The length of time after the 2.8* 1 loss of SWS flow to a component before that component may be damaged 000065 Loss of Instrument Air / 8 X AK3.08 - Actions contained in EOP for 3.7 1 loss of instrument air CE/E06 Loss of Main Feedwater / 4 X EA2.2 - Adherence to appropriate 3.0 1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 1

PWR RO Examination Outline Facility: PVNGS Printed: 05/05/2005 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000036 Fuel Handling Accident / 8 X AK2.01 - Fuel handling equipment 2.9 1 000060 Accidental Gaseous Radwaste Rel. / X AK1.01 - Types of radiation, their units 2.5 1 9 of intensity and the location of sources of radiation in a nuclear reactor power plant 000061 ARM System Alarms / 7 X AA2.05 - Need for area evacuation; check 3.5 1 against existing limits 000067 Plant Fire On-site / 9 X 2.1.20 - Ability to execute procedure 4.3 1 steps.

000068 Control Room Evac. / 8 X 2.1.10 - Knowledge of conditions and 2.7 1 limitations in the facility license.

000069 Loss of CTMT Integrity / 5 X AK3.01 - Guidance contained in EOP for 3.8* 1 loss of containment integrity CE/A11 RCS Overcooling - PTS / 4 X EA1.1 - Components, and functions of 3.3 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features CE/A13 Natural Circ. / 4 X EA2.2 - Adherence to appropriate 2.9 1 procedures and operation within the limitations in the facility's license and amendments CE/A16 Excess RCS Leakage / 2 X EK2.2 - Facility's heat removal systems, 3.0 1 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility K/A Category Totals: 1 2 1 1 2 2 Group Point Total: 9

PWR RO Examination Outline Printed:

Facility: PVNGS 05/05/2005 ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X K2.01 - RCPS 3.1 1 004 Chemical and Volume Control X K6.31 - Seal injection 3.1 1 system and limits on flow range 004 Chemical and Volume Control X A4.10 - Boric acid pumps 3.6 1 005 Residual Heat Removal X K5.03 - Reactivity effects 2.9* 1 of RHR fill water 006 Emergency Core Cooling X K3.01 - RCS 4.1* 1 007 Pressurizer Relief/Quench Tank X K5.02 - Method of forming 3.1 1 a steam bubble in the PZR 007 Pressurizer Relief/Quench Tank X K1.03 - RCS 3.0 1 008 Component Cooling Water X K1.02 - Loads cooled by 3.3 1 CCWS 008 Component Cooling Water X A4.01 - CCW indications 3.3 1 and controls 010 Pressurizer Pressure Control X K2.01 - PZR heaters 3.0 1 010 Pressurizer Pressure Control X A4.02 - PZR heaters 3.6 1 012 Reactor Protection X K4.09 - Separation of control 2.8 1 and protection circuits 013 Engineered Safety Features X K5.02 - Safety system logic 2.9 1 Actuation and reliability 022 Containment Cooling X A2.03 - Fan motor thermal 2.6 1 overload/high-speed operation 026 Containment Spray X K4.05 - Prevention of 2.8 1 material from clogging nozzles during recirculation 039 Main and Reheat Steam X K4.04 - Utilization of 2.9 1 steam pressure program control when steam dumping through atmospheric relief/dump valves, including 1

PWR RO Examination Outline Printed:

Facility: PVNGS 05/05/2005 ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points T-ave. limits 059 Main Feedwater X 2.1.1 - Knowledge of 3.7 1 conduct of operations requirements.

061 Auxiliary/Emergency X A1.02 - S/G pressure 3.3* 1 Feedwater 061 Auxiliary/Emergency X K6.01 - Controllers and 2.5 1 Feedwater positioners 062 AC Electrical Distribution X K3.01 - Major system loads 3.5 1 062 AC Electrical Distribution X A1.01 - Significance of D/G 3.4 1 load limits 063 DC Electrical Distribution X A2.01 - Grounds 2.5 1 064 Emergency Diesel Generator X K3.02 - ESFAS controlled or 4.2 1 actuated systems 064 Emergency Diesel Generator X 2.2.24 - Ability to analyze 2.6 1 the affect of maintenance activities on LCO status.

073 Process Radiation Monitoring X A2.02 - Detector failure 2.7 1 076 Service Water X A3.02 - Emergency heat 3.7 1 loads 078 Instrument Air X 2.4.11 - Knowledge of 3.4 1 abnormal condition procedures.

103 Containment X A3.01 - Containment 3.9 1 isolation K/A Category Totals: 2 2 3 3 3 2 2 3 2 3 3 Group Point Total: 28 1

PWR RO Examination Outline Printed:

Facility: PVNGS 05/05/2005 ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 001 Control Rod Drive X K2.05 - M/G sets 3.1* 1 002 Reactor Coolant X K5.08 - Why PZR level 3.4 1 should be kept within the programmed band 011 Pressurizer Level Control X A1.02 - Charging and 3.3 1 letdown flows 015 Nuclear Instrumentation X A4.01 - Selection of 3.6* 1 controlling NIS channel 017 In-core Temperature Monitor X K4.01 - Input to subcooling 3.4 1 monitors 033 Spent Fuel Pool Cooling X K1.05 - RWST 2.7* 1 034 Fuel Handling Equipment X A3.01 - Travel limits 2.5* 1 056 Condensate X A2.04 - Loss of condensate 2.6 1 pumps 071 Waste Gas Disposal X K3.04 - Ventilation system 2.7 1 086 Fire Protection X K6.04 - Fire, smoke, and 2.6 1 heat detectors K/A Category Totals: 1 1 1 1 1 1 1 1 1 1 0 Group Point Total: 10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 05/05/2005 Facility: PVNGS Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.16 Ability to operate plant phone, paging system, 2.9 1 and two-way radio.

2.1.27 Knowledge of system purpose and or function. 2.8 1 2.1.28 Knowledge of the purpose and function of major 3.2 1 system components and controls.

Category Total: 3 Equipment Control 2.2.11 Knowledge of the process for controlling 2.5 1 temporary changes.

2.2.27 Knowledge of the refueling process. 2.6 1 Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.

2.3.11 Ability to control radiation releases. 2.7 1 Category Total: 2 Emergency Procedures/Plan 2.4.13 Knowledge of crew roles and responsibilities 3.3 1 during EOP flowchart use.

2.4.19 Knowledge of EOP layout, symbols, and icons. 2.7 1 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 05/05/2005 Facility: PVNGS Form ES-401-3 Generic Category KA KA Topic Imp. Points 2.4.43 Knowledge of emergency communications systems 2.8 1 and techniques.

Category Total: 3 Generic Total: 10 1

PWR SRO Examination Outline Facility: PVNGS Printed: 05/05/2005 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000007 Reactor Trip - Stabilization - X EA2.01 - Decreasing power level, from 4.3 1 Recovery / 1 available indications 000015/000017 RCP Malfunctions / 4 X AA2.10 - When to secure RCPs on loss of 3.7 1 cooling or seal injection 000025 Loss of RHR System / 4 X AA2.02 - Leakage of reactor coolant 3.8 1 from RHR into closed cooling water system or into reactor building atmosphere 000040 Steam Line Rupture - Excessive Heat X AA2.05 - When ESFAS systems may be 4.5 1 Transfer / 4 secured 000058 Loss of DC Power / 6 X 2.4.4 - Ability to recognize abnormal 4.3 1 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

000062 Loss of Nuclear Svc Water / 4 X AA2.02 - The cause of possible SWS 3.6 1 loss K/A Category Totals: 0 0 0 0 5 1 Group Point Total: 6 1

PWR SRO Examination Outline Facility: PVNGS Printed: 05/05/2005 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000003 Dropped Control Rod / 1 X AA2.04 - Rod motion stops due to 3.6* 1 dropped rod 000028 Pressurizer Level Malfunction / 2 X AA2.03 - Charging subsystem flow 3.3 1 indicator and controller CE/A11 RCS Overcooling - PTS / 4 X 2.1.20 - Ability to execute procedure 4.2 1 steps.

CE/A16 Excess RCS Leakage / 2 X EA2.2 - Adherence to appropriate 3.7 1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 0 0 0 0 3 1 Group Point Total: 4 1

PWR SRO Examination Outline Printed:

Facility: PVNGS 05/05/2005 ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X 2.2.22 - Knowledge of 4.1 1 limiting conditions for operations and safety limits.

005 Residual Heat Removal X A2.04 - RHR valve 2.9 1 malfunction 012 Reactor Protection X A2.01 - Faulty bistable 3.6 1 operation 076 Service Water X A2.01 - Loss of SWS 3.7* 1 103 Containment X A2.04 - Containment 3.6* 1 evacuation (including recognition of the alarm)

K/A Category Totals: 0 0 0 0 0 0 0 4 0 0 1 Group Point Total: 5 1

PWR SRO Examination Outline Printed:

Facility: PVNGS 05/05/2005 ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 034 Fuel Handling Equipment X K1.05 - Shutdown monitor 3.4* 1 056 Condensate X A2.05 - Condenser tube 2.5* 1 leakage 072 Area Radiation Monitoring X 2.4.29 - Knowledge of the 4.0 1 emergency plan.

K/A Category Totals: 1 0 0 0 0 0 0 1 0 0 1 Group Point Total: 3 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 05/05/2005 Facility: PVNGS Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.6 Ability to supervise and assume a management role 4.3 1 during plant transients and upset conditions.

2.1.11 Knowledge of less than one hour technical 3.8 1 specification action statements for systems.

Category Total: 2 Equipment Control 2.2.25 Knowledge of bases in technical specifications for 3.7 1 limiting conditions for operations and safety limits.

2.2.34 Knowledge of the process for determining the 3.2* 1 internal and external effects on core reactivity.

Category Total: 2 Radiation Control 2.3.6 Knowledge of the requirements for reviewing and 3.1 1 approving release permits.

Category Total: 1 Emergency Procedures/Plan 2.4.26 Knowledge of facility protection requirements 3.3 1 including fire brigade and portable fire fighting equipment usage.

2.4.30 Knowledge of which events related to system 3.6 1 operations/status should be reported to outside agencies.

Category Total: 2 Generic Total: 7 1

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: 1 Op-Test No: 2005 Examiners: Operators:

Initial Conditions: IC #16, 50% power, MOC.

Turnover: Unit 1 has been at ~50% power for the past 3 days. The Unit had previously operated at near 100% power for 8 months. Power was reduced to perform repairs on A MFP. The repairs have been completed and the Unit is now waiting on a chemistry hold to increase power back to 100%. AF A is tagged out for maintenance. LCO 3.7.5. Condition b has been entered. Expected to be returned in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. HPSI A tagged out for bearing replacement. LCO 3.5.3 condition b was entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. Expected to be returned in approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. Train B is protected equipment. Normal Shiftly Surveillances are complete. EOOS action level is Orange.

Event Malf. No. Event Type* Event Description No.

1 ED04A C-SRO After turnover is complete, Startup Transformer NAN-X01 fails (Plant Event) requiring an evaluation of operability of AC offsite circuits, Tech Spec 3.8.1.1 operability must be performed within 1 hr.

2 TCNP01A C-CO After the crew evaluates TS for the SUT failure, TCW pump A bearing seizes.

This causes the A TCW Pump to trip on overcurrent. The Standby pump does not auto start. The crew should implement 41AL-1RK7A & 40AO-9ZZ03, Loss of Cooling Water, Section 5.0 and manually start the Standby TCW Pump.

3 I-RO/SRO After the crew addresses the loss of cooling water, the Reactor Regulating System TR04:RCNTT Hot Leg temperature transmitter 111X input fails low affecting the PZR Level 111X Control Setpoint. The crew should implement 40AO-9ZZ16, RRS Malfunctions, Section 3.0, and select the unaffected instrument for input.

4 C-RO/SRO While the crew is implementing 40AO-9ZZ16, the in-service letdown back-AV02:CHEP pressure control valve fails closed. The crew should implement 40AO-9ZZ05, V201Q Loss of Letdown, Section 3.0.

5 TH01A .01 C -RO/SRO After the crew places the alternate letdown back-pressure control valve in service, 5:00 an RCS leak in excess of Tech Spec limits occurs. The crew should implement CV06A 40AO-9ZZ02, Excessive RCS Leakrate, and evaluate T.S. 3.4.14. The normally running charging pump trips requiring the RO to start the E Charging Pump.

6 RD03I C- After the crew addresses the RCS leak, two CEAs drop partially into the core. A RO/CO/SRO reactor trip is automatically initiated. Two stuck CEAs require the RO to initiate RD03J M- All boration. The main turbine will fail to trip requiring the CO to manually trip it. The RD02A crew should implement 40EP-9EO01, Standard Post Trip Actions.

RD02C (Critical Task to establish reactivity control)

TC18 7 NoMSIS I-CO/RO After boration is initiated and the crew has transitioned to 40EP-9EO03, Loss of MMF TH01A M-All Coolant Accident. The leak degrades into a Large Break LOCA. MSIS fails to

.1 automatically actuate, requiring manual actuation. B HPSI fails to auto start on the SIAS condition and requires a manual start.

End Crew takes action to establish a cooldown.

point (Critical Task is to ensure adequate Safety Injection Actuation flow to meet Safety Function requirements within 30 minutes of entry into the LOCA procedure and after the Safety Injection Actuation setpoints are exceeded.)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 (Critical Task is to stop the RCPs on loss of subcooling.)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: 2 Op-Test No: 2005 Examiners: Operators:

Initial Conditions: IC #20, 100% power, MOC.

Turnover: Unit 1 has been at 100% power for the last 8 months. AF A is tagged out for maintenance. LCO 3.7.5.

Condition b has been entered. Expected to be returned in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. HPSI A tagged out for bearing replacement.

LCO 3.5.3 condition b was entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. Expected to return in approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. Normal Shiftly Surveillances are complete. Train B is protected equipment. EOOS action level is Orange.

Event Malf. No. Event Event Description No. Type*

1 IOR I-SRO After the crew assumes the shift, the crew receives a High Log Power ZDSBAC01HLO Trip on Channel 'A' along with the High Log Power Permissive alarm.

G OFF The crew should recognize that the log power channel has not failed, but the permissive is no longer bypassed. The CRS should address Tech Specs. LCO 3.3.1 condition 'c' applies due to the bypass removal being inoperable and bypass or trip the channel within 1 hr.

2 BK05:NANS02G R-RO After the crew takes the LCO action, a loss of NAN-S02G will occur causing a loss of one tower of cooling tower fans. (Plant Event) The N-CO/SRO CRS should enter 40AO-9ZZ12, Degraded Electrical and 40AO-9ZZ07, Degraded Vacuum. The crew determines a downpower is needed to stabilize vacuum.

After the crew completes the initial downpower, vacuum stabilizes.

3 I-RO After recovering from the loss of vacuum, a high failure of pressurizer TR01:RCNPT100 pressure instrument RCN-PT-100X occurs. This will require the crew X 2500 to address the alarm response procedure and select Channel Y on RCN-HS-100, PZR Pressure Control Selector, to ensure closer of the PZR spray valve.

4 CC01A C-CO/SRO After completing the actions for the PZR instrument failure, NCW Pump A will trip due to a ground fault. The Standby NCW pump CP05:NCNP01B will not start automatically or manually. This will require the CC01B operators to crosstie EW to NC IAW 40AO-9ZZ03, Loss of Cooling Water, Section 4.0. The CRS should address Tech Spec 3.7.7.

(Cascading T.S.)

C-RO/SRO The RO should respond to the loss of letdown and refer to 40AO-9ZZ05. The CRS should take action to keep PZR level below the Tech. Spec. limit of 56%.

5 RD04 M-All After the CRS has addressed Tech Specs, FWPT B alarms are received and the operator locally confirms high vibrations on the ATWS C-RO/CO pump. The CO takes action to trip the B MFW pump. Reactor Power Cutback automatically initiates but two of the CEAs fail to insert. The reactor fails to trip automatically or by manual pushbuttons. The crew will open L-03 & L-10 breakers to initiate the

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Rx Trip. All rods go in on the Reactor Trip. The crew should implement SPTAs.

(Critical Task to trip the Reactor)

The CRS should transition to the Rx Trip EOP.

6 ED02 C-CO During implementation of Rx Trip, a loss of offsite power occurs. The CRS should transition to the LOOP/LOFC EOP. Once the crew enters CP06:SPBP01 M-All the LOOP/LOFC procedure a loss of PBB-S04 will occur because the B Spray Pond trips requiring the operator to secure the B DG.

The CO will need to swap the S/G feed source from AF B to AFN-P01.

7 CP06:AFNP01 After the CO transitions to the N AF Pump, AFN-P01 will trip on an 86 Lockout. This will result in a loss of all feedwater.

8 C- The CRS should transition to the FRP procedure and restore power to SRO/RO/CO PBB-S04 using the A DG. The crew can then feed the SGs with AF B.

M-All (PRA Significant)

(Critical Task to ensure the required 4KV bus is energized to meet Safety Function requirements prior to the completion of the Maintenance of Vital Auxiliaries success path)

(Critical Task to establish feedwater to the unaffected SG)

End Crew stabilizes plant with AF B feeding at least one SG.

point

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: 3 Op-Test No: 2005 Examiners: Operators:

Initial Conditions: IC #20, 100% power, MOC.

Turnover: Unit 1 has been at 100% power for the last 8 months. AF A is tagged out for maintenance. LCO 3.7.5.

Condition b has been entered. Expected to be returned in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. HPSI A tagged out for bearing replacement.

LCO 3.5.3 condition b was entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. Expected to return in approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. Normal Shiftly Surveillances are complete. Train B is protected equipment. EOOS action level is Orange.

Event Malf. No. Event Event Description No. Type*

1 RCCPT101C I-SRO After the crew assumes the shift, the crew receives a high failure of C Channel Narrow Range Pressurizer Pressure Instrument. The crew should recognize the failure and respond with 41AL-1RK5A and T.S.

3.3.1.A. The crew takes action to bypass the affected parameters.

2 TH06A C-SRO After the crew takes the LCO action, a 30 gpd tube leak will start on

  1. 1 S/G. The crew should respond with 40AO-9ZZ02, Excessive RCS Leakrate, and notify chemistry. This Leakrate requires continued monitoring.

3 ED12B C- After the crew completes the applicable portions of 40AO-9ZZ02, RO/CO/SRO PNB-D26 will be lost. The CRS should implement 40AO-9ZZ13, Loss of Class Instrument or Control Power, and select the appropriate control instrument for PZR level control, stop one charging pump, and goes to 40AO-9ZZ05, Loss of Letdown. CO starts 40ST-9EC03 within one hour and set CEAC INOP flag in all operable CPCs. CRS refers to T.S. 3.8.9 and 3.4.9.

4 NI02C 0 I- After carrying out the actions for the loss of PNB-D26, Control RO/CO/SRO Channel #2 will fail low. The crew should address the alarm response NI02D 0 for the AMI received and respond IAW 40AO-9ZZ16, RRS Malfunction. The RO should take CEDMCS out of Auto Sequential and the CO should select the unaffected channel on RRS panel and place CEDMCS back to Auto Sequential. The CO will then take Control Channel #2 FWCS input to maintenance and remove the ATUN lockout.

5 TH06A N- After completing the actions for the loss of Control Channel #2, the RO/CO/CRS S/G tube leak will degrade to 200 gpd. This will require the CRS to commence a plant Shutdown IAW 40OP-9ZZ05. T.S. 3.4.14.

6 TR01:RCNTT111Y I- CO During the shutdown the leak rate will degrade requiring a Unit Trip.

650 The crew should enter the SPTAs, 40EP-9EO01. Upon entering the M-All SPTAs, the Tave input to the FWCS will fail high causing the ruptured SG to be overfed. The CO will need to take action to minimize feed to the SG.

7 RP07B C-RO/SRO Train B BOP ESFAS Sequencer failure will occur on the trip. The RO should respond by manually starting B Train Safety Injection

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 and Support Equipment.

(Critical Task is to start B HPSI pump.)

M-All After completing the SPTAs, the CRS should transition to the SGTR EOP, 40EP-9EO04 and proceeds to cooldown and isolate the ruptured S/G.

(Critical Task is to ensure the crew prevents a release of steam to atmosphere from the ruptured S/G during the RCS cooldown.)

(Critical Task is to ensure the crew isolates the most affected S/G within 30 minutes of entry into the SGTR procedure.)

End Crew isolates the affected SG.

point (Critical Task is to ensure the crew takes action to prevent the Main Steam Safety Valves on the most affected S/G from opening after the most affected S/G has been isolated.)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9

PVNGS License Examination Administrative Topics Outline PVNGS Form ES-301-1 Facility: Palo Verde Date of Examination: 7/29/05 - 8/5/05 Examination Level: RO Operating Test Number: PVNGS RO Administrative Topic Type Describe activity to be performed: K/A #

(see Note) Code* IMP C, N Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain Conduct of Operations performance data. 2.1.25 (Candidate will be required to calculate the required SDM 2.8 using procedures and given plant parameters)

Scheduled as Admin Task RA1-1. (NEW)

C, D Ability to use plant computer to obtain and evaluate Conduct of Operations parametric information on system or component status. 2.1.19 (Candidate will be required to calculate NKBDELT). 3.0 Scheduled as Admin Task RA1-2. (AD010)

C, N Knowledge of tagging and clearance procedures.

(Candidate will determine tagging boundaries for a 2.2.13 Equipment Control permit) 3.6 Schedule as Admin JPM RA2. (NEW)

C, M Verify administrative and radiological entry requirements per the RWP (Candidate will be required to demonstrate Radiation Control the proper method for verifying qualifications and identify 2.3.1 the proper REP, task, and dose settings/limits for the 2.6 particular job assignment.)

Scheduled as Admin JPM RA3.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs: 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

(S)imulator Confidential Page 1 05/05/05

PVNGS License Examination PVNGS Form ES-301-1 Administrative Topics Outline Facility: Palo Verde Date of Examination: 7/29/05 - 8/5/05 Examination Level: SRO Operating Test Number: PVNGS SRO Administrative Topic Type Describe activity to be performed: K/A #

(see Note) Code* IMP C, M Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data. 2.1.25 Conduct of Operations (Candidate will be required to review a SDM surveillance 3.1 Test, indentify 3 errors and any required action)

Scheduled as Admin Task SA1-1.

C, N Ability to locate and use procedures and directives related to shift staffing and activities.

(Candidate will be required to determine that operator is to 2.1.5 Conduct of Operations not able to stand watch and that the operator will need a 3.4 working hour limit deviation form to permit helping with surveillance)

Scheduled as Admin Task SA1-2. (NEW)

C, D Knowledge of tagging and clearance procedures.

2.2.13 Equipment Control (Tech Review a Permit and determine three errors) 3.8 Schedule as Admin JPM SA2.

C, D Verify administrative and radiological entry requirements per the RWP (Candidate will be required to demonstrate the proper method for verifying qualifications and identify 2.3.1 Radiation Control 3.0 the proper REP, task, and dose settings/limits for the particular job assignment.)

Scheduled as Admin JPM SA3.

S, M Ability to take action called for in the Emergency Plan, including acting as Emergency Coordinator. (Candidate 2.4.38 Emergency Plan will classify event and perform initial Emergency 4.0 Coordinator duties.)

Scheduled as Admin JPM SA4.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol room (D)irect from bank ( 3 for ROs: 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

(S)imulator Confidential Page 1 05/05/05

PVNGS License Examination PVNGS Form ES301-2 Control Room/In-Plant Systems Outline Facility: PVNGS_ Date of Examination: 8/1/05 Exam Level: RO_ Operating Test No.: RO Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

JPM # System/JPM Title Type Code* Safety Function SAM JS1 Respond to a SIT Low Lvl alarm & Refill 3.2.006A4.02 4.0/3.8 2 Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the SAD JS2 Unit Auxiliary Transformer MAN-X02 3.6.062.A4.07 3.1/3.1 6 SLN JS3 Perform BDAS Alarm Check (Appendix 8) w/i one 3.7.015.A3.03 3.9/3.9 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (Time Critical)

SADL JS4 Vent off the high pressure in the reactor vessel head to 3.2.002.K4.05 3.8/4.2 3 the RDT. (RC001)

SAM JS5 Perform a Boration of the RCS (CH002 Modify, BAMP 3.1.004A4.01 3.8/3.9 1 Dish Press Lo Alarm received) Plant Event Reconnect and reset the Steam Bypass Control System SD 4 JS6 (SF006) 3.4.041.A4.08 3.0/3.1 (Secondary)

SN JS7 Respond to Containment Sump Trouble Excessive 3.5.103.A4.01 3.2/3.3 5 Runtime Alarm 41AL-1RK7B SD JS8 Vent the Containment (CP001) 8 3.8.029.A103 3.0/3.3 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

AEM JP1 Return a Battery Charger to Service (Attachment 97-A) 3.6.063.A4.02 2.8*/2.9 6 3.6.063.K1.03 2.9/3.5 Line up a Borated Water Source during Control Room DER 1 JP2 Fire (PRA Significant) (AO017) 4.2.068.AA1.11 4.0/4.3 Restore local air to the SFP gate seals and place the EMPR JP3 Nitrogen bottles on standby (Plant Modification) 3.8.078.A3.01 3.1/3.2 8 3.8.078.K4.02 3.2/3.5

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (L)ow-Power 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator Confidential Page 1

PVNGS License Examination PVNGS Form ES301-2 Control Room/In-Plant Systems Outline Facility: PVNGS Date of Examination: 8/1/05 Exam Level: SRO Operating Test No.: SROU Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

JPM # System/JPM Title Type Code* Safety Function SAM JS1 Respond to a SIT Low Lvl alarm & Refill 3.2.006A4.02 4.0/3.8 2 Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the SAD JS2 Unit Auxiliary Transformer MAN-X02 3.6.062.A4.07 3.1/3.1 6 SLN JS3 Perform BDAS Alarm Check (Appendix 8) w/i one 3.7.015.A3.03 3.9/3.9 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (Time Critical)

In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

AEM JP1 Return a Battery Charger to Service (Attachment 97-A) 3.6.063.A4.02 2.8*/2.9 6 3.6.063.K1.03 2.9/3.5 Line up a Borated Water Source during Control Room DER 1 JP2 Fire (PRA Significant) (AO017) 4.2.068.AA1.11 4.0/4.3

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (L)ow-Power 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator Confidential Page 1

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 7/29/05 - 8/05/05 Operating Test No.: 2005 A E Scenarios P V P E 1 2 3 4 T M L N (SPARE) O I I T CREW POSITION CREW POSITION CREW POSITION CREW POSITION T N C A I A T L M N Y S A B S A B S A B S A B U T P R T O R T O R T O R T O M E O C P O C P O C P O C P RO RX 0 0 0 0 1*

NOR 0 1 1 1 1*

SRO-I I/C 4 3 5 7 4*

MAJ 2 3 2 5 2 SRO-U TS 2 2 3 4 2 RO RX 0 0 0 0 1*

NOR 0 1 1 1 1*

SRO-I I/C 5 4 3 9 4*

MAJ 2 3 2 5 2 SRO-U TS 0 0 0 0 NA RO RX 0 1 0 1 1*

NOR 0 0 1 0 1*

SRO-I I/C 3 4 3 7 4*

MAJ 2 3 2 5 2 SRO-U TS 0 0 0 0 NA Instructions:

1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.
  • Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirement.

Author: _Phillip Capehart _______________________

NRC Reviewer: _ ________________________

ES-301 Competencies Checklist Form ES-301-6 OPERATING TEST NO.: PVNGS 2005 SROU RO BOP (CO)

Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 1,2,3 1,2,4 1,2,3 3,4,5 2,3,4 2,3,4 2,6,7 2,4,5 2,3,4 and Conditions 4,5,6 5,6,8 4,5,6 6,7 5,6,8 5,6,7 6,7,8 5,6,7 7 7 Comply With and 1,2,3 1,2,4 1,2,3 3,4,5 2,3,4 2,3,4 2,5,6 2,4,5 2,3,4 Use Procedures (1) 4,5,6 5,6,8 4,5,6 6,7 5,6,8 5,6,7 7 6,8 5,6,7 7 7 Operate Control NA NA NA 3,4,5 2,3,4 3,4,5 2,6,7 2,4,5 3,4,5 Boards (2) 6,7 5,6,8 6,7 6,8 6,7 Communicate and 1,2,3 1,2,3 1,2,3 3,4,5 2,3,4 2,3,4 2,6,7 2,4,5 2,3,4 Interact 4,5,6 4,5,6 4,5,6 6,7 5,6,8 5,6,7 6,7,8 5,6,7 7 7,8 7 Demonstrate Supervisory 1,2,3 1,2,4 1,2,3 NA NA NA NA NA NA Ability (3) 4,5,6 5,6,8 4,5,6 7 7 Comply With and 1,5 1,4,5 1,3,5 NA NA NA NA NA NA Use Tech. Specs. (3)

Notes:

(1) Includes technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Author: Phillip Capehart ___________________________

NRC Reviewer: ____________________________

NUREG-1021, Revision 9

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